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Category:Letter type:NL
MONTHYEARNL-21-034, Notification of Expected Date of Transfer of Ownership of Nuclear Units to Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; and Notification of Receipt of All Required Regulatory Approvals2021-05-26026 May 2021
Notification of Expected Date of Transfer of Ownership of Nuclear Units to Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; and Notification of Receipt of All Required Regulatory Approvals
NL-21-039, Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary2021-05-20020 May 2021
Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary
NL-21-033, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2021-05-11011 May 2021
Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel
NL-21-032, Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission at Indian Point Energy Center2021-05-11011 May 2021
Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission at Indian Point Energy Center
NL-21-005, Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions2021-05-11011 May 2021
Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions
NL-21-030, Submittal of 2020 Annual Radiological Environmental Operating Report2021-05-0606 May 2021
Submittal of 2020 Annual Radiological Environmental Operating Report
NL-21-027, Registration of Spent Fuel Cask Use2021-04-20020 April 2021
Registration of Spent Fuel Cask Use
NL-21-021, Registration of Spent Fuel Cask Use2021-04-19019 April 2021
Registration of Spent Fuel Cask Use
NL-21-017, Pre-Notice of Disbursement from Decommissioning Trusts2021-04-0808 April 2021
Pre-Notice of Disbursement from Decommissioning Trusts
NL-21-010, Submittal of 2020 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report2021-02-17017 February 2021
Submittal of 2020 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report
NL-21-006, Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement2021-02-10010 February 2021
Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement
NL-21-014, Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2021-01-26026 January 2021
Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device
NL-20-082, Notice of Planned Transfer of Decommissioning Funds2020-12-14014 December 2020
Notice of Planned Transfer of Decommissioning Funds
NL-20-081, Pre-Notice of Disbursement from Decommissioning Trusts2020-12-0909 December 2020
Pre-Notice of Disbursement from Decommissioning Trusts
NL-20-080, Report in Accordance with 10 CFR 71.95(a) for Failure to Comply with Certificate of Compliance No. 71-93212020-11-19019 November 2020
Report in Accordance with 10 CFR 71.95(a) for Failure to Comply with Certificate of Compliance No. 71-9321
NL-20-079, (IP2 and IP3) - Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-12012 November 2020
(IP2 and IP3) - Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic
NL-20-077, Submittal of Quality Assurance Program Manual Revision 22020-11-0909 November 2020
Submittal of Quality Assurance Program Manual Revision 2
NL-20-078, Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-11-0909 November 2020
Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device
NL-20-076, Revision of Commitment Related to Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Issue Regarding Spent Fuel Dispersal2020-11-0202 November 2020
Revision of Commitment Related to Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Issue Regarding Spent Fuel Dispersal
NL-20-069, One-time Scheduler Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency2020-10-0808 October 2020
One-time Scheduler Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency
NL-20-070, Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-10-0202 October 2020
Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device
NL-20-067, Redacted Version of Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-09-16016 September 2020
Redacted Version of Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline
NL-20-064, 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments2020-09-0101 September 2020
10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments
NL-20-060, Status of Remaining Actions for Generic Letter 2004-022020-08-11011 August 2020
Status of Remaining Actions for Generic Letter 2004-02
NL-20-057, Cancellation of Commitment Related to Large Break LOCA Reanalysis2020-07-30030 July 2020
Cancellation of Commitment Related to Large Break LOCA Reanalysis
NL-20-0851, 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material2020-07-22022 July 2020
30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material
NL-20-051, Submittal of Quality Assurance Program Manual, Revision 1 for the Indian Point Energy Center2020-07-0707 July 2020
Submittal of Quality Assurance Program Manual, Revision 1 for the Indian Point Energy Center
NL-20-052, Unsatisfactory 10 CFR 26 Fitness-For-Duty Blind Performance Testing Results2020-07-0707 July 2020
Unsatisfactory 10 CFR 26 Fitness-For-Duty Blind Performance Testing Results
NL-20-012, Application to Revise Provisional Operating License and Technical Specifications2020-06-30030 June 2020
Application to Revise Provisional Operating License and Technical Specifications
NL-20-050, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-06-24024 June 2020
Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline
NL-20-041, Registration of Unit 3 Spent Fuel Cask Use2020-05-13013 May 2020
Registration of Unit 3 Spent Fuel Cask Use
NL-20-042, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2020-05-12012 May 2020
Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel
NL-20-033, Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2020-04-28028 April 2020
Technical Specifications Proposed Change - Permanently Defueled Technical Specifications
NL-20-038, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-04-23023 April 2020
Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline
NL-20-035, Response to Request for Additional Information - Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic2020-04-16016 April 2020
Response to Request for Additional Information - Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic
NL-20-034, Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic2020-04-13013 April 2020
Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic
NL-20-021, Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-03-24024 March 2020
Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device
NL-20-020, Submittal of 2019 Annual Fitness for Duty Performance Data Report Update2020-02-26026 February 2020
Submittal of 2019 Annual Fitness for Duty Performance Data Report Update
NL-20-015, Submittal of 2019 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report2020-02-10010 February 2020
Submittal of 2019 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report
NL-20-008, Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Fuel Handling Building Crane2020-01-0606 January 2020
Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Fuel Handling Building Crane
NL-19-094, 2018 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report2019-12-16016 December 2019
2018 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report
NL-19-084, Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments2019-11-21021 November 2019
Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments
NL-19-093, Proposed Technical Specifications (TS) Changes - Indian Point Nuclear Generating Unit 3 TS SR 3.7.7.2 and TS 3.7.6, Required Action A.12019-11-21021 November 2019
Proposed Technical Specifications (TS) Changes - Indian Point Nuclear Generating Unit 3 TS SR 3.7.7.2 and TS 3.7.6, Required Action A.1
NL-19-092, Request for Rescission of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-11-20020 November 2019
Request for Rescission of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
NL-19-043, Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.122019-10-22022 October 2019
Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.12
NL-19-073, Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-10-22022 October 2019
Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
NL-19-078, Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2019-10-22022 October 2019
Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications
NL-19-091, Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Cask Use2019-10-17017 October 2019
Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Cask Use
NL-19-090, Registration of Unit 2 Spent Fuel Cask Use2019-10-0909 October 2019
Registration of Unit 2 Spent Fuel Cask Use
NL-19-079, 50.59(d)(2) Summary Report of Changes, Tests and Experiments2019-09-26026 September 2019
50.59(d)(2) Summary Report of Changes, Tests and Experiments
2021-05-06
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Text
Entergy Nuclear Northeast
-Entergy Entergy Nuclear Operations, Inc.
Entergy Nuclear Indian Point 2, LLC P. 0. Box 249 Buchanan, NY 10511 July 15, 2003 Re: Indian Point Unit No. 2 Docket No. 50-247 NL-03-116 US Nuclear Regulatory Commission Attn: Document Control Desk Mail Station O-P1-17 Washington, DC 20555-0001
SUBJECT:
Supplement 5 to the Indian Point 2 License Amendment Request for Conversion to Improved Standard Technical Specifications
References:
- 1) Entergy letter (NL-02-016) to NRC, "License Amendment Request (LAR 02-005) Conversion to Improved Standard Technical Specifications," dated March 27, 2002
- 2) Entergy letter (NL-02-092) to NRC, Supplement 1 to the Indian Point 2 License Amendment Request for Conversion to Improved Standard Technical Specifications," dated July 10, 2002
- 3) Entergy letter (NL-03-035) to NRC, "Supplement 2 to the Indian Point 2 License Amendment Request for Conversion to Improved Standard Technical Specifications," dated February 26, 2003
- 4) Entergy letter (NL-03-081) to NRC, "Supplement 3 to the Indian Point 2 License Amendment Request for Conversion to Improved Standard Technical Specifications," dated May 19, 2003
- 5) Entergy letter (NL-03-107) to NRC, "Supplement 4 to the Indian Point 2 License Amendment Request for Conversion to Improved Standard Technical Specifications," dated June 26, 2003
- 6) Staff Requests for Additional Information regarding References 1, 2, 3, 4, and 5, and associated Entergy responses (see Attachment 2)
Dear Sir:
By letter dated March 27, 2002 (Reference 1), as supplemented by letters dated July 10, 2002, February 26, 2003, May 19, 2003, and June 26, 2003 (References 2, 3, 4, and 5 respectively), Entergy Nuclear Operations, Inc. (Entergy) requested to amend the Indian Point 2 (P2) Plant Operating License, Appendices A and B, "Technical Specifications." The proposed amendment converts the P2 Current Technical Specifications (CTS) to Improved Technical Specifications (ITS) in accordance with NUREG 1431, "Standard Technical Specifications-Westinghouse Plants," Rev. 2.
$0o (
NL-03-1 16 Page2of4 References 1, 2, 3, 4, and 5 indicated that the proposed ITS amendment would be periodically supplemented, as necessary, to incorporate approved amendments to the CTS. In addition, Entergy has made changes in response to Requests for Additional Information (RAls) from the Nuclear Regulatory Commission (NRC) staff. The purpose of this supplement is to incorporate changes required by RAI responses, Technical Specification Task Force (TSTF) Traveler 359, and to include specific values for the Allowable Values. Attachment 1 to this supplement provides an index of the ITS sections that are affected by incorporation of these changes. , "Correspondence History of Responses to Requests for Additional Information," provides a list of staff RAIs and the corresponding Entergy responses.
These letters described the changes that were made to the proposed ITS. To facilitate staff review, Entergy is attaching the RAls and responses to each affected section of this supplement. , "List of Pending License Amendment Requests (LARs) not Reflected in ITS Submittal and Supplements," shows amendment requests currently under review by the NRC staff. Entergy requests continued processing of the proposed LARs in parallel with the review of the ITS submittal as supplemented. Additional supplemental submittals incorporating these LARs, when approved, will be made as required. These supplements will be coordinated with the NRC staff reviewers to ensure that the ITS review is not adversely impacted.
As was done with References 1, 2, 3, 4, and 5, the material constituting Supplement 5 to the ITS submittal is enclosed herewith on CD-ROM. The Supplement 5 CD-ROM includes the following:
All the information originally transmitted by References 1, 2, 3, 4, and 5; A copy of this supplemental cover letter and attachments; and
- The IP2 CTS through Amendment 237.
This supplemental letter and the CD-ROM were prepared in accordance with the guidance provided in NRC Regulatory Issue Summary 2001-05, Guidance on Submitting Documents to the NRC by Electronic Information Exchange or on CD-ROM."
As previously described, the RAI responses have, in some cases, resulted in new or revised no significant hazards determination evaluations and these revised evaluations have been included with the associated specification packages. However, this supplement has not changed the conclusion that the conversion of the Indian Point 2 Technical Specifications to Improved Technical Specifications involves no significant hazards consideration as defined by 10 CFR 50.92.
In accordance with 10 CFR 50.91, a copy of this submittal and the associated attachments are being submitted to the designated New York State official.
/I
NL-03-1 16 Page 3 of 4 There are no commitments contained in this letter.
Should you or your staff have any questions regarding this matter, please contact me at (914) 734-5336.
Sincerely, 6
William S. Blair
.J 1P2 ITS Project Manager Enclosure Attachments cc: see page 4
NL-03-116 Page 4 of 4 cc: (w/o enclosure)
Mr. Hubert J. Miller Regional Administrator-Region I US Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1498 Mr. Patrick D. Milano, Senior Project Manager Project Directorate 1-1 Division of Licensing Project Management US Nuclear Regulatory Commission Mail Stop 0-8-2C Washington, DC 20555-0001 Senior Resident Inspector Indian point 2 US Nuclear Regulatory Commission PO Box 38 Buchanan, NY 10511 Mayor, Village of Buchanan 236 Tate Avenue Buchanan, NY 10511 Mr. Paul Eddy NYS Department of Public Service 3 Empire Plaza Albany, NY 12223 Mr. William M. Flynn, President NYS ERDA Corporate Plaza West 286 Washington Ave. Extension Albany, NY 12223-6399
ATTACHMENT 1 TO NL-03-116 List of Sections Included In Supplement 5 Entergy Nuclear Operations, Inc.
Indian Point Unit No. 2 Docket No. 50-247
Attachment 1 NL-03-116 Page 1 of 1 Revised Supplement 5 Sections 3.3.1 - Rev. 2, Supp. 5 3.3.2 - Rev. 2, Supp. 5 3.3.3 - Rev. 2, Supp. 5 3.3.4 - Rev. 2, Supp. 5 3.3.5 - Rev. 2, Supp. 5 3.3.6 - Rev. 2, Supp. 5 3.3.7 - Rev. 2, Supp. 5 3.5.3 - Rev. 3, Supp. 5
ATTACHMENT 2 TO NL-03-116 Correspondence History of Responses to Requests for Additional Information Entergy Nuclear Operations, Inc.
Indian Point Unit No. 2 Docket No. 50-247
Attachment 2 NL-03-116 Page 1 of 2
- 1) RAI: NRC letter to Entergy Nuclear Operations, Inc., "Request for Additional Information (RAI) Regarding Section 3.6 (Containment Systems) of the Improved Technical Specifications (ITS) (TAC No. MB4739)," dated August 6, 2002 Response: Entergy letter (NL-02-130) to NRC, "Response to Request for Additional Information Regarding Section 3.6 (Containment Systems) of the Improved Technical Specifications (ITS)," dated October 10, 2002
- 2) RAI: NRC letter to Entergy Nuclear Operations, Inc., "Request for Additional Information (RAI) Regarding Section 3.6 (Containment Systems) of the Improved Technical Specifications (ITS) (TAC No. MB4739)," dated August 6, 2002 Response: Entergy letter (NL-02-133) to NRC, "Response to Request for Additional Information Regarding Section 5.5.14 of the Improved Technical Specifications (ITS)," dated October 28, 2002
- 3) RAI: NRC letter to Entergy Nuclear Operations, Inc., "Request for Additional Information (RAI) Regarding Section 3.5.3 - Emergency Core Cooling System (ECCS) - Shutdown - The Improved Technical Specifications Beyond Scope Issue No. 1 (TAC No. MB5062)," dated September 26, 2002 RAI: NRC letter to Entergy Nuclear Operations, Inc., Request for Additional Information (RAI) Regarding Section 3.8.3 - Diesel Fuel Oil and Starting Air -
Beyond Scope Issue No. 8 (TAC No. MB5069)," dated October 3, 2002 RAI: NRC letter to Entergy Nuclear Operations, Inc., "Request for Additional Information (RAI) Regarding Section 3.7.8 - Service Water System - Beyond Scope Issue No. 6 (TAC No. MB5067)," dated October 10, 2002 RAI: NRC letter to Entergy Nuclear Operations, Inc., Request for Additional Information (RAI) Regarding Improved Technical Specification (ITS) Beyond Scope Issue No. 9, ITS Section 3.8.4 DC Sources - Operating (TAC No.
MB5070)," dated October 17, 2002 RAI: NRC letter to Entergy Nuclear Operations, Inc., "Comments and Request for Additional Information (RAI) Regarding Improved Technical Specification (ITS)
Beyond Scope Issues (BSI)-S1, BSI-S2, BSI-S3, BSI-S4, BSI-S5 and BSI-S6 (TAC Nos. MB6394, MB6395, MB6396, MB6397, MB6398, and MB6399)," dated October 17, 2002 Response: Entergy letter (NL-02-148) to NRC, "Response to Request for Additional Information Regarding Sections 3.3.1, 3.5.3, 3.7.8, 3.8.3, 3.8.4, and 3.8.6 of the Improved Technical Specifications (ITS)," dated November 26, 2002
Attachment 2 NL-03-116 Page 2 of 2
- 4) RAI: NRC letter to Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Unit No. 2 - Comments and Request for Additional Information (RAI)
Regarding Improved Technical Specification (ITS) Sections 1.0, 2.0, 3.0, 3.1, 3.2, 3.3, 3.4, 3.5, 3.6, 3.7, 3.9, 4.0, and 5.0 (TAC No. MB4739)," dated October 22, 2002 Response: Entergy letter (NL-02-160) to NRC, "Response to Request for Additional Information Regarding Sections 1.0, 2.0, 3.0, 3.1, 3.2, 3.3, 3.4, 3.5, 3.6, 3.7, 3.9, 4.0, and 5.0 of the Improved Technical Specifications (ITS)," dated December 18, 2002
- 5) RAI: NRC letter to Entergy Nuclear Operations, Inc., "Request for Additional Information (RAI) Regarding Section 3.8.1 - AC Sources Operating - Beyond Scope Issue No. 7 (TAC No. MB5068)," dated December 31, 2002 Response: Entergy letter (NL-03-002) to NRC, "Response to Request for Additional Information Regarding Section 3.8.1, AC Sources Operating, of the Improved Technical Specifications (ITS)," dated January 27, 2003
- 6) RAI: NRC letter to Entergy Nuclear Operations, Inc., "Request for Additional Information (RAI) Regarding Improved Technical Specification (ITS) Sections:
3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation; ITS 3.3.3, Post Accident Monitoring Instrumentation; 3.3.4, Remote Shutdown Instrumentation; 3.3.5, Loss of Power Diesel Generator (LOP-DG) Start Instrumentation; 3.3.6, Containment Purge and Exhaust Isolation Instrumentation; 3.3.7 Control Room Ventilation System (CRVS) Actuation Instrumentation (TAC No. MB4739)," dated January 22, 2003 Response: Entergy letter (NL-03-052) to NRC, "Response to Request for Additional Information Regarding Section 3.3, Instrumentation, of the Improved Technical Specifications (ITS)," dated April 8, 2003
- 7) RAI: NRC letter to Entergy Nuclear Operations, Inc., "Request for Additional Information (RAI) Regarding Section 3.7 - Plant Systems (TAC No. MB4739),"
dated May 16, 2003 Response: Entergy letter (NL-03-103) to NRC, "Response to Request for Additional Information Regarding Section 3.7, Plant Systems, of the Improved Technical Specifications (ITS)," dated June 23, 2003
ATTACHMENT 3 TO NL-03-116 List of Pending License Amendment Requests (LARs) not Reflected In ITS Submittal and Supplements Entergy Nuclear Operations, Inc.
Indian Point Unit No. 2 Docket No. 50-247
Attachment 3 NL-03-116 Page 1 of 1 Letter No. LAR Title and Date NL-02-042 License Amendment Request (LAR-02-007) - Changes to Effectively 05/30/02 Coordinate Indian Point Units 1 and 2 Programs
